Text

Proposed Scenarios for the Duane Arnold Retake Examination - April 2008
	ML082900536
Person / Time
Site:	Duane Arnold
Issue date:	04/22/2008
From:	Mcneil D; NRC/RGN-III/DRS/OLB
To:	; Duane Arnold
References
	50-331/08-301
	Download: ML082900536 (41)
	v • d • e

______________________________________________________________________________

ES-301 Competencies Checklist Form ES-301-6 Facility: DAEC Date of Examination: 21 April, 2008 Operating Test No.: 2008-301 APPLICANTS RO : RO RO RO SRO-I SRO-I : SRO-I SRO-I SRO-U SRO-U SRO-U SRO-U Competencies SCENARIO SCENARIO SCENARIO SCENARIO 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 Interpret/Diagnose 2,3, 4,7 2,3,4, 5,7,8 Events and Conditions Comply With and ALL ALL Use Procedures (1)

Operate Control 1,2,3, 5,6,7 N/A Boards (2)

Communicate ALL ALL and Interact Demonstrate N/A ALL Supervisory Ability (3)

Comply With and N/A 2,4 Use Tech. Specs. (3)

Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

Instructions:

Check the applicants license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant.

QF-1030-19 Rev. 12 Appendix D Scenario Outline Form ES-D-1 Facility: DAEC Scenario No.: 1 Op-Test No.: 2008-301 Examiners: Operators:

N/A N/A N/A N/A Initial Conditions: ~90% power, with a RR increase scheduled, Turnover:

Saturday, Dayshift. Warm spring day. There are no extra operators today.

Event Malf. Event Event No. No. Type* Description 1 N/A Reactivity Raise RR flow to increase reactor power to full power.

2 NM08 I/C APRM Failure (Downscale).

Feed Regulating Valve locks up. The FRV lockup can be 3 FW16 I/C reset.

Major Condenser Air In leakage starts (slowly, eventually will get 4 MC04A bigger) (AOP entry)

AOP Normal Fast power reduction IAW IPOI-4. Above MELLA. AOP 5 N/A Rx 255.2 AOP 6 N/A EOP Reactor Scram - Entry into EOP 1 and IPOI 5 MS08B Major Steam Leak in Steam Tunnel with failure of MSIVs to auto 7 close - Entry into EOP 3. (Critical Task)

MS20 EOP

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Retention: Life of policy = 10yrs. Disposition: Reviewer and Approver Retain in: Training Program File 2008 NRC ILT ESG 1 Page 1 of 18

QF-1030-19 Rev. 12 2008 NRC Scenario #1 ESG, Rev. 0 (Merta Retake)

EXAMINATION SENARIO GUIDE (ESG)

SITE: DAEC RAISE RR FLOW / APRM FAILURE DOWNSCALE / FRV LOCKUP - RECOVER /

SLOW LOSS OF VACUUM / FAST POWER 2008 REV. 0 REDUCTION / IPOI 5 / EOP 1 / STEAM LEAK IN ESG ILT 01 STEAM TUNNEL - FAILURE TO AUTO ISOLATE PROGRAM: OPERATIONS #:

COURSE: INITIAL LICENSE TRAINING #: 50007 TOTAL TIME: 90 MINUTES 2008 NRC ILT ESG 1 Page 2 of 18

QF-1030-19 Rev. 12 2008 NRC Scenario #1 ESG, Rev. 0 (Merta Retake)

GUIDE REQUIREMENTS The goal of this scenario is to evaluate ILT students during the NRC Goal of Exam with 3 man crew.

Training:

There are no formal learning objectives Learning Objectives:

None Prerequisites:

Simulator Training Simulator Booth Instructor Resources: Phone Talker Evaluators (or Floor Instructor)

1. AOP 691, Rev. 4

References:

2. ARP 1C05A, D-2, Rev. 60

3. ARP 1C05A, F-1, Rev. 60

4. ARP 1C07A, D-10, Rev. 32

5. ARP 1C07B, B-1, Rev. 64

6. ARP 1C07B, C-1, Rev. 64

7. ARP 1C07B, D-9, Rev. 64

8. EOP 1, Rev. 15

9. IPOI 4, Rev. 97

10. IPOI 5, Rev. 48

11. EOP 3, Rev. 19 Commitments:

Dynamic Simulator Evaluation Method:

None Operating Experience:

2008 NRC ILT ESG 1 Page 3 of 18

QF-1030-19 Rev. 12 2008 NRC Scenario #1 ESG, Rev. 0 (Merta Retake)

QUANTITATIVE ATTRIBUTES (Use this form for NRC/INPO Evaluations only as required to document associated quantitative information.)

Malfunctions:

Before EOP Entry:

1. APRM Downscale

2. Feed Regulating Valve Lockup

3. Condenser air in-leakage After EOP Entry:

1. Steam Leak in Steam Tunnel

2. Failure of MSIVs to Isolate Abnormal Events:

1. Condenser backpressure rise (air in-leakage)

Major Transients:

1. Rising condenser backpressure

2. Steam Leak in Steam Tunnel Critical Tasks:

1. Manually Isolate MSIVs to isolate the leak in the Reactor Building (MSIVs failed to auto isolate.)

2008 NRC ILT ESG 1 Page 4 of 18

QF-1030-19 Rev. 12 2008 NRC Scenario #1 ESG, Rev. 0 (Merta Retake)

SCENARIO

SUMMARY

Current plant operating status:

The plant is operating at 87% power.

Scenario segments:

Raising RR flow to increase reactor power. This is the reactivity event for the RO. When the ILT Examiner is satisfied, then the scenario can continue.

ARPM Downscale Failure. The C APRM will fail downscale. The RO will follow ARP actions, while the CRS will address Technical Specifications.

Respond to an inadvertently locked-up Feed Reg Valve by resetting it in accordance with ARP 1C05A , F-1.

While the operators are involved with resetting the Feed Regulating Valve lockup, the main condenser will develop a slow air leak. The loss of vacuum will be at a rate that allows them to work through the AOP for Rising Condenser Backpressure (AOP 691) and the ARPs for HI BACK PRESSURE (1C07B, D-9, 1C07B, B-1, and 1C07B, C-1). The condenser backpressure will be degrading for 14 minutes without audible alarm. The Offgas high flow will come in at ~14 minutes.

Step 3 of AOP 691 will direct the crew to perform a Fast Power Reduction per IPOI 4 Section 6.0. The fast power reduction will place the plant above the MELLA line, requiring entry into AOP 255.2.

As the condenser back pressure continues to increase, it will approach 7.5" Hg abs.,

forcing the operators to insert a Manual Scram and perform IPOI 5 actions. The manual scram will also cause them to enter into EOP 1 on low RPV water level. Once the crew scrams, main condenser vacuum improves due to the reduction of heat load.

Following the reactor scram a steam leak will develop in the Steam Tunnel. The MSIVs will fail to auto isolate the leak, and will require the crew to manually shut the MSIVs.

2008 NRC ILT ESG 1 Page 5 of 18

QF-1030-19 Rev. 12 2008 NRC Scenario #1 ESG, Rev. 0 (Merta Retake)

SCENARIO OUTLINE:

BOOTH INSTRUCTOR ACTIONS 1 SIMULATOR SET UP: (perform set up per the Simulator Setup Checklist, including entering actions items per the Simulator Input Summary.)

1.1 General Instructions

a. Copy the IC file to the directory where IC files are kept. If this file is not available, then:

a) Reset to IC 20.

b) Lower reactor power with RR flow [RR controllers are at ~74.5 in manual]

c) Input the below listed Malfunctions and Remotes into the simulator console.

b. Place the simulator in run.

c. Pump the Drywell sumps.

d. Complete the Attachment 6 of OTI 101, Exam Scenario Checklist.

1.2 EVENT TRIGGER DEFINITIONS:

Trigger No. Trigger Logic Statement Trigger Word Description 2,3,4,7 Manual Manually Inserted MALFUNCTIONS:

Time Malf. No. Malfunction Title Delay Ramp ET Initial Final Value Value Setup MS20A GROUP I ISOLATION 0 0 N/A TRUE TRUE VALVE(S) FAIL(S) TO CLOSE- CV4412 Setup MS20B GROUP I ISOLATION 0 0 N/A TRUE TRUE VALVE(S) FAIL(S) TO CLOSE- CV4413 Setup MS20C GROUP I ISOLATION 0 0 N/A TRUE TRUE VALVE(S) FAIL(S) TO CLOSE- CV4415 Setup MS20D GROUP I ISOLATION 0 0 N/A TRUE TRUE VALVE(S) FAIL(S) TO CLOSE- CV4416 Setup MS20E GROUP I ISOLATION 0 0 N/A TRUE TRUE VALVE(S) FAIL(S) TO CLOSE- CV4418 2008 NRC ILT ESG 1 Page 6 of 18

QF-1030-19 Rev. 12 2008 NRC Scenario #1 ESG, Rev. 0 (Merta Retake)

Time Malf. No. Malfunction Title Delay Ramp ET Initial Final Value Value Setup MS20F GROUP I ISOLATION 0 0 N/A TRUE TRUE VALVE(S) FAIL(S) TO CLOSE- CV4419 Setup MS20G GROUP I ISOLATION 0 0 N/A TRUE TRUE VALVE(S) FAIL(S) TO CLOSE- CV4420 Setup MS20H GROUP I ISOLATION 0 0 N/A TRUE TRUE VALVE(S) FAIL(S) TO CLOSE- CV4421 Setup NM08C APRM CHANNEL FAILS- 0 0 2 As Is 0 CHNL C Setup FW16A FW REG VALVE LOCKUP- 0 0 3 FALSE TRUE FWRV A Setup MC04A MAIN CONDENSER AIR 0 01:00 4 0 0.6 INLEAKAGE-LP CONDENSER Setup MS08B STEAM LEAKAGE IN 0 2:00 7 0 0.3 STEAM TUNNEL LINE B

1.4 OVERRIDES

None 1.5 REMOTE FUNCTIONS:

None FLOOR INSTRUCTOR ACTIONS 2 Simulator Pre-brief:

2.1 Individual position assignments 2.2 Simulator Training Changes Since Last Module 2.3 Simulator hardware and software modifications/problems that may impact examination 2008 NRC ILT ESG 1 Page 7 of 18

QF-1030-19 Rev. 12 2008 NRC Scenario #1 ESG, Rev. 0 (Merta Retake) 4 TURNOVER INFORMATION Day of week and shift Saturday, Day shift Weather conditions Warm spring day (Plant power levels) 87 % Pwr MWt 1664 MWe 550 CORE FLOW 39.5 Thermal Limit Problems/Power Evolutions None Plant Risk Status CDF Baseline Color Green Existing LCOs, date of next surveillance None STPs in progress or major maintenance No STPs in progress Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment No equipment taken out or returned to service.

Comments, evolutions, problems, core damage frequency, etc.

There are no extra operators.

Reactor power was lowered to make a rod adjustment. The adjustment is complete.

As soon as you take the shift, raise power with RR flow to 1840 MWth.

2008 NRC ILT ESG 1 Page 8 of 18

Rev. 0 2008 NRC Scenario #1 SCENARIO TIME-LINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Shift Turnover COMPLETE TURNOVER: Get familiar with plant conditions.

Provide Shift Turnovers to the SRO

SRO will provide beginning of shift brief to coordinate the tasks that and ROs.

were identified on the shift turnover.

a. Review applicable current Plant Status

b. Review relevant At-Power Risk status

c. Review current LCOs not met and Action Requirements

d. Verify crew performs walk down of control boards and reviews turnover checklists 2008 NRC ILT ESG 1 page 9 of 18

Rev. 0 2008 NRC Scenario #1 SCENARIO TIME-LINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #1 Booth Instructor respond as plant SRO personnel and respond as necessary.

Raises Power Provides a reactivity brief.

10% using Communicates with Real Time Desk and System Operating Center.

Recirculation Flow Provide direct oversight of power increase.

The Examiner RO will indicate Raises power with Recirc Pump Flow Controllers IAW IPOI-3, Section 4.

when to move on to Event 2. 1. To raise recirc flow, set the digital display to the S PERCENT SPEED DEMAND variable by pressing the display switch, then rotate the A[B]

MG SET SPEED CONTROL SIC 9245A[B] knobs on 1C04 clockwise in small equal increments.

2. Keep loop flows balanced by comparing the Recirc Pump discharge flow on FI 4634A vs. FI 4634B or Pen 1 vs. Pen 2 on FR 4635.

Monitors critical plant parameters - power, pressure, level BOP Monitors balance of plant equipment.

Provides peer check for RO during power increase.

2008 NRC ILT ESG 1 page 10 of 18

Rev. 0 2008 NRC Scenario #1 SCENARIO TIME-LINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 2 Booth Instructor: RO:

APRM C Fails

Responds to the APRM DOWNSCALE annunciator for C APRM, downscale 1C05A D-2.

Activate ET 2 TRUE

Note: Other indications are ARPM C reading downscale, APRM C Insert malfunction NM08C at 0% severity DNSC light lit on apron section of 1C05, B002 and B003 Computer with no ramp. This fails the C APRM to Points alarm on the alarm monitor, and both show Purple on GD15 (if zero. shown on one of the computer monitors).

Role Play as FIN team or I&C and inform CRS:

the control room that you will start

Initiates investigation of the failure developing a troubleshooting plan.

Initiate a WRC,

Complies with Tech. Specs. and TRM.

ATC/BOP ROs:

With CRS permission, bypass C APRM IAW OI 878.4, Section 6.1.

Verifies APRM Mode Selector Sw on 1C37 in OPERATE

Verify the APRM UPSCALE, INOP, and DOWNSCALE Trips are RESET at 1C37

Verify the IRM/ARPM recorders on the 1C05 panel indicate approximately the same average power for the bypassed APRM as the unbypassed APRM channels.

Places the APRM BYPASS switch for the A,C,E APRMs to the NEUTRAL position.

Observes that the bypass light on 1C05 and 1C37 are OFF

Place the APRM bypass switch for the C APRM to the C position

Observes that the bypass lights for the C APRM on ON at 1C05 and 1C37 2008 NRC ILT ESG 1 page 11 of 18

Rev. 0 2008 NRC Scenario #1 SCENARIO TIME-LINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 3 Begin the transient by toggling RO Feed Reg Valve Perform actions of ARP 1C05[A], F-1 for CV-1579 Lockup Activate ET 3 to TRUE

Stop all power changes

Control Reactor Water Level as necessary (various means described in the Annunciator Response Procedure.

On prompting of Role play as NSPEO sent to check the A

Send an operator to check for air leaks.

the Examiner, Feed Reg Valve:

insert the Event

Have operator check ZC-1579 positioner LCD display for error codes Found a WCC operator hanging a Section Trigger to start CRS Tag on V30-572 (air to A Feed Reg Valve)

Event 4. This rather than on V30-972 for CV-6334.

Direct / supervise actions of ARP 1C05[A], F-1 event takes ~15 RO minutes before Reset CV-1579 and return to Automatic operation as follows:

the first alarm IF asked about error codes, error code 10 (although the is displayed, unless the air has been

Verify the controller LED displays for the locked FRV are lit crew may restored, then no error codes are

Verify the FW Lockout Relay amber light above the lockout relay is DIM notice the displayed.

For the Hand Controller HC-1579:

vacuum loss prior to that)

Verify HC-1579 is in MANUAL When directed to restore

Select Y on the display

Adjust the Y bias setting to zero Delete malfunction FW16A

Determine the appropriate M/A station controller output signal using ZI-1579 and Attachment 1 of ARP Role Play as NSPEO to verify that the

At HC-1579, perform the following:

LED display for the locked FRV are ON

Select V and adjust V to the value obtained using Attachment 1.

Reset the Lockout Relay

Verify the amber light is no longer lit.

Transfer CV-1579 to AUTO per ARP directions (matching individual controller to master controller and select AUTO.

2008 NRC ILT ESG 1 page 12 of 18

Rev. 0 2008 NRC Scenario #1 SCENARIO TIME-LINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 4 Booth Instructor: BOP Condenser Air Activate ET 4

Respond to annunciator 1C07A, D10 OFFGAS PANEL 1C-34 In-Leakage This will begin the condenser air inleakage TROUBLE.

on a ramp of 60 seconds to 0.6. This will

Goes to 1C34 to respond to the problem per the appropriate ARP.

begin a very slow backpressure rise. It takes approximately 14 minutes to reach

Checks out Offgas Flow and Condenser Back Pressure on 1C07.

the first alarm (OG Trouble, due to SJAE

Starts checking the ARPs for possible high back pressure alarm actions, high flow). With no operator action, the 5 (1C07B, D-9, 1C07B, B-1, 1C07B, C-1).

backpressure alarms will come in 23 minutes later. This slow degradation of vacuum allows the crew to use AOP 691. RO NOTE: When the crew performs a fast power reduction per IPOI 4, the

If directed, start a power reduction at normal rates.

backpressure starts to go down again.

Booth Instructor: CRS WHEN the crew performs Fast Power

May direct that power reduction be started at normal rates.

Reduction (OR at the discretion of the Examiner):

Enters AOP 691.

Change MC04A to 0.8 with NO RAMP This increase the backpressure degradation.

Role Play:

If sent to change the SJAE lineups, report back in 30 minutes that you have completed the action that they directed since these actions would be transparent to the control room operators.

If sent to look for the vacuum leak, report back in 30 minutes that you cannot find the leak.

2008 NRC ILT ESG 1 page 13 of 18

Rev. 0 2008 NRC Scenario #1 SCENARIO TIME-LINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 4 If power reduction has not been previously BOP Condenser Air started the condenser high back pressure

Determine how fast main condenser pressure is increasing In-Leakage alarms will come in,

Verify steam seals / Offgas System / SJAE for proper operation (Cont) 1C07B, D-9 first, then 1C07B, B-1,

Verify Circulating Water System operation is normal.

followed by 1C07B, C-1.

Operate all available Cooling Tower fans.

RO

Commence turbine load reduction by performing IPOI 4 Section 6.0 Booth Instructor: FAST POWER REDUCTION.

Change the value of Malfunction MC04A

Determine position on the power to flow map after lowering power with as directed by the examiner to move the Recirc to 27Mlbm/hr.

scenario along. Increase only malfunction

Inform the CRS that the plant is above the MELLA line, if theres time (VI), increase by increments of 0.1.

following the Fast Power Reduction.

Experience has showed that 0.9 will bring backpressure up at a reasonable rate.

When condenser pressure cannot be maintained less the 7.5" Hg abs.,

manually scram the reactor if power is greater than 30%.

Event 5

Perform AOP 255.2 actions when directed by CRS.

Fast Power Reduction

Place one APRM in each trip system in FAST SPEED

Monitor for undamped oscillations

Verify proper indications and operation of various systems

Verify control rod positions

Demand an official case

When power is stable, plot operating point on power/flow map CRS

Directs the crew to enter and perform AOP 691.

Directs the RO to perform, FAST POWER REDUCTION.

Directs the crew to enter and perform AOP 252.

Directs the RO to insert a manual scram.

2008 NRC ILT ESG 1 page 14 of 18

Rev. 0 2008 NRC Scenario #1 SCENARIO TIME-LINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 6 Booth Instructor: RO Reactor Scram

Perform immediate operator responses to a reactor scram.

NOTE: Once the reactor is scrammed After the scram and the main turbine trips, the

Determine when an EOP 1 entry condition exists, and inform CRS backpressure will recover, such that the value should not challenge the MSIV BOP closure value. This sets up the next event.

Perform EOP Defeat 11.

SRO If directed to recharge the main condenser Direct crew response for performance of initial EOP 1 actions (RC).

water seal:

Role play as the aux operator. Wait one

Direct entry into EOP 1.

minute then use Remote Function MC13

Direct operator actions to scram the reactor and perform the IPOI 5 to OPEN and report that you are charging immediate actions.

the main condenser water seal.

Direct crew response for performance of RC/P leg of EOP 1.

Direct operator actions to cooldown the reactor at less than 100 °F/hr.

2008 NRC ILT ESG 1 page 15 of 18

Rev. 0 2008 NRC Scenario #1 SCENARIO TIME-LINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 7 Booth Instructor BOP Steam Leak in Activate ET 7

Respond to alarms and indications.

Steam Tunnel Ensure MS08A goes active to 0.3 with a

1C04B D-4, Steam Leak Det. Hi T 60 second ramp, which causes a small

1C04B B-4, Steam Leak Det. Hi Temp steam line break outside primary containment (in steam tunnel).

Diagnose the steam leak is in the steam tunnel.

Booth Instructor:

Recognize that the Main Steamline Isolation Valves did not isolate.

RO Watch DW temperature (there is a Monitor file) to ensure that Steam Tunnel

Respond to alarms and indications.

temperature gets to at least 200°F (N/A

1C05A A-8, PCIS Channel A Steam Tunnel Hi Temp once the MSIVs are closed). 200°F is the

1C05B A-7, PCIS Channel B Steam Tunnel Hi Temp where the annunciators will come in to alert the RO that the leak is in the steam

1C05B A-8, PCIS Group 1 Isolation Initiated tunnel, and a group 1 should have

Recognize that the Main Steamline Isolation Valves did not isolate.

occurred.

SRO

Enter EOP 3 and direct required actions.

Direct that the MSIVs be closed manually.

When the plant Booth Instructor:

is stable and FREEZE the simulator and announce to reactor the crew that the scenario is complete.

pressure and level are being controlled IAW EOP 1

- - END OF SCENARIO ***

2008 NRC ILT ESG 1 page 16 of 18

SEG Validation Checklist SEG ________2008 NRC ILT Scenario #1____________ Rev. ______0_______

Correct IC or plant status identified.

Shift turnover forms filled out (both CRS/OSM and NSOE) if required.

Additional documents are prepared (STPs, Work Orders, LCO Paperwork).

Tasks and Objectives have been verified to be correct.

Plant PRA initiating events, important equipment and important tasks are identified.

SOMS tags identified and included in setup instructions.

Special setup instructions identified; handswitch manipulations, procedure markups, alarm borders, 3D case available, computer points substituted, etc.

Setup files correctly called out.

Malfunction list is accurate.

Override list is accurate.

Remote function list is accurate.

Event triggers are accurate.

Time/Notes section is accurate and includes all reasonable cues that may be given to initiate an action. Cues are unambiguous and provide a definitive moment to take action.

Instructor Activity section is accurate and complete:

Actions are clearly defined for Booth or Floor instructor.

Role-playing is clearly noted.

The sequence of events is completely and concisely narrated even if it takes no instructor action.

Automatic actions that require verification are noted.

Reasonable alternate paths are considered and included.

Event trigger activation is distinguished from narrative text (Bold font)

Noun descriptions of actions that occur on event trigger initiation are complete, for example set ET 3 to TRUE which activates malfunction SW21C resulting in a loss of the C Well Water Pump.

Other simulator control actions are clearly distinguished from narrative text, for example after drywell temperature reaches 280 deg. F SNAP the simulator to IC 0.

Student and Instructor copies of worksheets or other training activities are verified correct and electronically attached to the file if appropriate.

2008 NRC ILT ESG 1 Page 17 of 18

SEG Validation Checklist SEG ________2008 NRC ILT Scenario #1____________ Rev. ______0_______

Expected Student Response Section is accurate and complete:

Critical tasks are accurate and clearly identified. Probable critical tasks are also listed with logical connection to the scenario; for example If the crew fails to get all the rods inserted before ED the critical task becomes (N/A as appropriate)

Tasks are clearly noted and properly numbered as appropriate.

Knowledge objectives are clearly noted and properly numbered as appropriate.

Expected as well as probable student responses are listed with logical connection to the scenario. (N/A as appropriate)

Actions are appropriately delineated by position(s); OSM, CRS, STA, RO, NSOE, Fire Brigade Leader, At the Controls Operator, etcetera. (N/A as appropriate)

Success paths are procedurally driven unless specific training not requiring procedures is desired and delineated. Procedural discrepancies are identified and corrected before training is given.

Responses for all communications to simulated personnel outside the Control Room are included, based on procedural guidance and standard operating practices.

Actions are listed using a logical order; by position and chronology. (N/A as appropriate)

Operating Experience, Human Performance Tools and Operator Fundamentals topics are included when appropriate.

Crew Performance Criteria follow the same chronology as the student responses, are complete and accurate. (For ESGs only)

For Walkthrough and Training Mode Scenarios with pre-planned pauses, sufficient information is presented to allow the instructor to meet the goal of the training.

Turnover information (as required) is correct:

Day and shift are appropriate.

Weather conditions do not conflict with malfunctions.

Power levels are correct.

Thermal limit problems and power evolutions are realistic and include a reason for any downpower.

Existing LCOs include start date, remaining time and actions.

Plant Risk Assessment (CDF and Color).

STPs are appropriate for day and shift.

Core Damage Frequency has been properly calculated and listed to 3 decimal places.

Maintenance is realistic for plant conditions.

Comments, evolutions, problems, etc, includes extra personnel (licensed/non-licensed if necessary), any condition that affects the flow of the scenario and any condition that does not fit in another category.

SME/Instructor Date SME/Instructor Date 2008 NRC ILT ESG 1 Page 18 of 18

SEG Validation Checklist SEG ________2008 NRC ILT Scenario #1____________ Rev. ______0_______

Crew: Instructors:

OSM ____________________________ Booth ________________________________

CRS ____________________________ Floor __________________________

STA __________________________________ Extra ________________________________

1C05 ____________________________

1C03 ____________________________

BOP ____________________________

Crew Comment:

Resolution:

Crew Comment:

Resolution:

NOTE: Following approval of SEGs, this page may be discarded.

SEG Validation Checklist SEG ________2008 NRC ILT Scenario #1____________ Rev. ______0_______

Crew Comment:

Resolution:

Crew Comment:

Resolution:

Crew Comment:

Resolution:

NOTE: Following approval of SEGs, this page may be discarded.

QF-1030-19 Rev. 12 Appendix D Scenario Outline Form ES-D-1 Facility: DAEC Scenario No.: 2 Op-Test No.: 2008-301 Examiners: Operators:

N/A N/A N/A N/A Initial Conditions: The plant is operating at 97% power and HPCI is tagged out due to failing the Quarterly Surveillance (did not come up to rated speed in time), LCO day 2 of 14.

Turnover:

Saturday, Dayshift. Warm spring day. I&C continues to work on HPCI ramp generator.

No other activities are planned. RCIC, 1D1, 1D10, 1D14 and 1D120 are protected. There are no extra operators today. A Manual Scram surveillance is to be performed (A side is the only side needing to be performed.)

Event Malf. No. Event Event No. Type* Description Perform STP 3.3.1.1-21, Manual Scram Functional Test on 1 N/A Normal channel A3.

Panel I/C Perform STP 3.3.1.1-21, Manual Scram Functional Test on 2 channel B3. The channel fails to insert the 1/2 scram. This Override TS leads to a Tech Spec entry.

I/C GSW pump trips. Auto start of the standby pump fails, but 3 SW01 may be manually started.

AOP The CRS will receive a phone call stating that System Engineering has evaluated a vendor notification that the B 4 N/A TS SBDG contains a main circuit board in its Voltage Regulator is faulty and cannot be counted on to work properly. This notification only effects the B SBDG.

Loss of Coolant Accident in DW. Entry into EOP 1 and 5 RR15 Major EOP 2 6 N/A EOP Spray DW due to High Temperature (Critical Task) 7 FW02 I/C Loss of high pressure feed Contingency Perform Alternate Level Control Emergency 8 N/A EOP Depressurization (Critical Task)

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Retention: Life of policy = 10yrs. Disposition: Reviewer and Approver Retain in: Training Program File 2008 NRC ILT ESG 2 Page 1 of 18

QF-1030-19 Rev. 12 2008 NRC Scenario #2 ESG, Rev. 0 (Merta Retake)

SIMULATOR EXERCISE GUIDE (SEG)

SITE: DAEC STP 3.3.1.1-21 MANUAL SCRAM FUNCTIONAL

/ GSW PUMP TRIP / B SBDG INOP / LOCA IN 2008 REV. 0 DW / SPRAY DW ON TEMPERATURE / LOSS ESG ILT 02 OF HIGH PRESSURE FEED / ALC ED PROGRAM: OPERATIONS #:

COURSE: INITIAL LICENSE TRAINING #: 50007 TOTAL TIME: 90 MINUTES 2008 NRC ILT ESG 2 Page 2 of 18

QF-1030-19 Rev. 12 2008 NRC Scenario #2 ESG, Rev. 0 (Merta Retake)

GUIDE REQUIREMENTS The goal of this scenario is to evaluate ILT students during the NRC Goal of Exam with 3 man crew.

Training:

There are no formal learning objectives Learning Objectives:

None Prerequisites:

Simulator Training Simulator Booth Instructor Resources: Phone Talker Evaluators (or Floor Instructor)

1. STP 3.3.1.1-21, Rev 3

References:

2. AOP 411, Rev 20.

3. EOP 1, Rev 15

4. EOP 2, Rev 14

5. ARP 1C06A C-4, Rev 50

6. ARP 1C06A B-3, Rev 50 Commitments:

Dynamic Simulator Evaluation Method:

None Operating Experience:

2008 NRC ILT ESG 2 Page 3 of 18

QF-1030-19 Rev. 12 2008 NRC Scenario #2 ESG, Rev. 0 (Merta Retake)

QUANTITATIVE ATTRIBUTES (Use this form for NRC/INPO Evaluations only as required to document associated quantitative information.)

Malfunctions:

Before EOP Entry:

1. Manual Scram Functional Test on Channel B3 Fails to Insert Scram

2. GSW Pump Fails, Standby GSW Pump Does Not Start Automatically After EOP Entry:

1. Loss of High Pressure Feedwater (RCIC stays on, but is unable to maintain RPV level)

Abnormal Events:

1. GSW pump trip Major Transients:

1. LOCA in DW Critical Tasks:

1. Spray the DW IAW EOP-2 on High DW Temperature

2. Perform Alternate Level Control Emergency Depressurization IAW EOP-1 and EOP-ED 2008 NRC ILT ESG 2 Page 4 of 18

QF-1030-19 Rev. 12 2008 NRC Scenario #2 ESG, Rev. 0 (Merta Retake)

SCENARIO

SUMMARY

Current plant operating status:

The plant is operating at Full power. HPCI is tagged out due to failing the Quarterly Surveillance (it did not come up to rated speed in time.) LCO day 2 of 14.

Scenario segments:

STP 3.3.1.1-21, Manual Scram Functional Test will be run on Channel A3. This channel will be successful.

STP 3.3.1.1-21, Manual Scram Functional Test will be run on Channel B3. This channel will fail this test. This will result in a Technical Specification entry. TS 3.3.1.1 Condition A.

The B GSW pump trips and the A GSW fails to auto start. The pump will start when the operator starts it manually (step one of AOP 411 LOSS OF GSW, immediate actions)

The CRS will receive a phone call from the SBDG System Engineer. The SE will inform the CRS that the B SBDG contains a main circuit board in its voltage regulator, and the vendor has contacted us and informed us that the circuit board is faulty, and cannot be counted on to work properly. The A SBDG is NOT effected by this problem. This will result in the B SBDG being declared INOP.

A LOCA will develop in the Drywell. This will result in the reactor being scrammed, and entry into EOP-1 and EOP-2.

Due to the LOCA, the DW will heat up to the point that requires DW spray to be implemented. Initiating DW sprays before 280°F is a Critical Task.

After the DW sprays are initiated, a loss of all high pressure feedwater will occur (RCIC stays running, but will be unable to maintain level), which, in conjunction with the LOCA, will force the CRS to enter the ALC leg of EOP-1, and eventually direct an Emergency Depressurization due to low level. The ALC ED being performed before -25 is a Critical Task.

2008 NRC ILT ESG 2 Page 5 of 18

QF-1030-19 Rev. 12 2008 NRC Scenario #2 ESG, Rev. 0 (Merta Retake)

SCENARIO OUTLINE:

BOOTH INSTRUCTOR ACTIONS 1 SIMULATOR SET UP: (perform set up per the Simulator Setup Checklist, including entering actions items per the Simulator Input Summary.)

1.1 General Instructions

a. Copy the IC file to the directory where IC files are kept. If this file is not available, then:

a) Reset to IC 20.

b) Verify the B and C GSW pumps are running and the A is off.

c) Input the Malfunctions and Remotes listed below

b. Place the simulator in run.

c. Pump the Drywell sumps.

d. Hang a MIP tag on the HPCI Aux. Oil Pump and place in PTL.

e. Hang MIP tags on the following HPCI valves: MO2202 and MO2239.

f. Have a copy of STP 3.3.1.1-21 available. Mark off section 6.0 in its entirety.

g. Have a copy of STP 3.8.1-01 available (not marked up).

h. Have a copy of STP 3.8.1-02 available (not marked up).

i. Complete OTI 101, Attachment 6, Exam Scenario Checklist 1.2 EVENT TRIGGER DEFINITIONS:

Trigger No. Trigger Logic Statement Trigger Word Description 3,5,7, 8, 10, Manual Manually Inserted 12,13

1.3 MALFUNCTIONS

Time Malf. No. Malfunction Title Delay Ramp ET Initial Final Value Value Setup SW37A GSW Pump 1P89A Fail To 0 N/A N/A TRUE TRUE Auto-Actuate Setup SW01B B GSW Pump Trip 0 N/A 3 FALSE TRUE AS DIR RR15B RECIRC LOOP B RUPT, 25:00 5 0 20 LOCA As Dir FW02A Condensate Pump Trip- 0 N/A 7 False TRUE Pump A As Dir FW02B Condensate Pump Trip- 0 N/A 8 False TRUE Pump B 2008 NRC ILT ESG 2 Page 6 of 18

QF-1030-19 Rev. 12 2008 NRC Scenario #2 ESG, Rev. 0 (Merta Retake)

Time Malf. No. Malfunction Title Delay Ramp ET Initial Final Value Value As Dir AN 1C03C(4) 1C03C (A-04) Annunciator 0 0 10 Crywolf On Box (4HX9W)

As Dir AN 1C03C(6) 1C03C (A-06) Annunciator 0 0 10 Crywolf On Box (4HX9W)

As Dir AN 1C03C (B-03) Annunciator 0 0 10 Crywolf On 1C03C(12) Box (4HX9W)

1.4 OVERRIDES

Time Override No. Override Title Delay Ramp ET Initial Final Value Value Setup DI HP HS-2239 MO 2239 Steam Isolation N/A N/A N/A N/A CLOSE HS Setup LO HP HS-2239(1) HS 2239 Green light N/A N/A N/A N/A OFF Setup LO HP HS-2239(2) HS 2239 Red light N/A N/A N/A N/A OFF Setup LO HP MO-2239(1) MO 2239 PCIS Green light N/A N/A N/A N/A OFF Setup LO HP MO-2239(2) MO 2239 PCIS Red light N/A N/A N/A N/A OFF Setup DI HP HS-2256 Aux Oil Pump 1P-218 HS N/A N/A N/A N/A OFF Setup LO HP HS-2256(1) Aux Oil Pump HS Green N/A N/A N/A N/A OFF light Setup LO HP HS-2256(2) Aux Oil Pump HS Red light N/A N/A N/A N/A OFF Setup DI HP HS-2202 Turbine Steam Supply HS N/A N/A N/A N/A CLOSE Setup LO HP HS-2202(1) HS 2202 Green light N/A N/A N/A N/A OFF Setup LO HP HS-2202(2) HS 2202 Red light N/A N/A N/A N/A OFF Setup LO MS PCIS GP 6B Logic All N/A N/A N/A N/A OFF PCIS-LBVHPCI Valves Closed Setup LO MS PCIS GP 6A Logic All N/A N/A N/A N/A OFF PCIS-LAVHPCI Valves Closed Setup AO HP PI-2207 0-1500PSIG Turb Inlet N/A N/A N/A N/A 0 Pressure Setup RP C71AS3B Reactor Manual Scram N/A N/A N/A OFF OFF System B As Dir FW HS-1401 Cond Pump 1P-8A N/A N/A 12 NAST NASP As Dir FW HS-1411 Cond Pump 1P-8B N/A N/A 13 NAST NASP 1.5 REMOTE FUNCTIONS:

None 2008 NRC ILT ESG 2 Page 7 of 18

QF-1030-19 Rev. 12 2008 NRC Scenario #2 ESG, Rev. 0 (Merta Retake)

FLOOR INSTRUCTOR ACTIONS 2 Simulator Pre-brief:

2.1 Individual position assignments 2.2 Simulator Training Changes Since Last Module 2.3 Simulator hardware and software modifications/problems that may impact training 2008 NRC ILT ESG 2 Page 8 of 18

QF-1030-19 Rev. 12 2008 NRC Scenario #2 ESG, Rev. 0 (Merta Retake) 4 TURNOVER INFORMATION Day of week and shift Saturday, Day shift Weather conditions Warm spring day (Plant power levels) 99 % Pwr MWt 1839 MWe 630 CORE FLOW 46.4 Thermal Limit Problems/Power Evolutions None Plant Risk Status CDF 1.450 x 10-5 Color YELLOW Existing LCOs, date of next surveillance HPCI, Day 2 of 14, for failure to achieve rated speed during the regularly scheduled Quarterly STP.

STPs in progress or major maintenance Last shift performed STP 3.3.1.1-22 , the Auto Scram functional, but didnt get the Manual Scram Channel STP done. They did perform the prerequisites. Perform STP 3.3.1.1-21 when you assume the watch.

I&C work continues on the HPCI ramp rate generator.

Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment No equipment taken out or returned to service.

Work continues on HPCI.

Comments, evolutions, problems, core damage frequency, etc.

RCIC, 1D1, 1D10, 1D14, 1D12, 1D120 in service charger, both SBDGs, both ESW, 1VAC011, 1VAC012, 1A3, and 1A4 are protected.

There are no extra operators.

2008 NRC ILT ESG 2 Page 9 of 18

Rev. 0 2008 NRC Scenario #2 SCENARIO TIME-LINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #1 Booth Instructor: SRO A Manual Gives Pre-job brief to coordinate and discuss evolution Scram Role Play as necessary to support the Surveillance STP.

Channel A3 RO Completes A Manual Scram Surveillance (Section 7.1 of the procedure)

BOP Acts as peer checker for RO 2008 NRC ILT ESG 2 page 10 of 18

Rev. 0 2008 NRC Scenario #2 SCENARIO TIME-LINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event #2 Booth Instructor: CRS B Manual Continues to supervise the evolution.

Scram Role Play as necessary to support the Surveillance STP.

Channel B3 RO Attempts to complete the B Manual Scram Surveillance (Section 7.2 of the procedure). When the manual scram button is depressed, the expected 1/2 scram will NOT occur.

Communicates the failure of the STP to the CRS.

BOP Acts as peer checker for RO CRS Consults Technical Specifications and determines that entry into TS 3.3.1.1 Condition A is applicable. This is a 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to trip the channel specification.

2008 NRC ILT ESG 2 page 11 of 18

Rev. 0 2008 NRC Scenario #2 SCENARIO TIME-LINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 3 Booth Instructor: BOP GSW Pump Start the GSW problem as follows:

Respond to annunciators 1C06A, C-4 B GSW PUMP 1P-89B TRIP OR Trip without MOTOR OVERLOAD, and 1C06B, B-3 GSW PUMPS 1P89A/B/C DISCH Auto Start HEADER LO PRESSURE.

Activate Event Trigger 3.

Respond to GSW abnormal operating condition.

This will trip the B GSW pump, and the A GSW pump will fail to auto start, but

ARP 1C06A, C-4 directs the operator to AOP 411, which directs that may be manually started. the standby pump be started so that the system alignment is with two pumps running.

Role Play:

ARP 1C06A, B-3 directs the operator to verify the low pressure 55 psig), Verify the auto start of the standby pump, and perform AOP As the NSPEO sent to the breaker and 411, Loss of GSW.

after approximately three minutes report that the B GSW pump breaker 1A409 CRS tripped on instantaneous over current.

Directs crew response to the partial loss of GSW per AOP 411.

If sent to the Pump House wait about 5

Directs/verifies the starting of a second GSW pump.

minutes and report that the pump looks

Has the operator verify there is sufficient GSW cooling flow.

normal. This is to simulate a fault in the wiring between the pump and the breaker

Verifies the MSIVs are still open.

Initiates an AR and a Work Request Card due to the failure of the A If asked, the GSW strainer is rotating, with GSW pump to auto-start when required.

a d/p reading of 0.7 psid.

Roll play as Electrical Maintenance personnel will be sent out to the plant.

2008 NRC ILT ESG 2 page 12 of 18

Rev. 0 2008 NRC Scenario #2 SCENARIO TIME-LINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 4 Booth Instructor: CRS Technical Consults Technical Specifications and determines that entry into TS 3.8.1 Role Play:

Specification condition B is appropriate.

Phone Call As the SBDG System Engineer (Don Westindorf), call the CRS and inform him

RA 3.8.1 B.1 requires SR 3.8.1.1 be completed within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

that we have received a vendor notification

RA 3.8.1 B.2 requires no further action at this time, due to the only that the B SBDG voltage regulator system being INOP is HPCI (a single train system, therefore not applying contains a circuit board that is faulty. The to B.2) circuit board cannot be counted on to work properly. The A SBDG is NOT effected

RA 3.8.1 B.3 requires that a common cause analysis be performed, but by this vendor notification. information from System Engineer has confirmed that this is NOT a common cause issue.

RA 3.8.1 B.4 requires SR 3.8.1.2 be performed for the operable SBDG once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

RA 3.8.1 B.5 requires restoration of the INOP SBDG within 7 days (and 8 days from an off site circuit being declared INOP) 2008 NRC ILT ESG 2 page 13 of 18

Rev. 0 2008 NRC Scenario #2 SCENARIO TIME-LINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 5 Booth Instructor Crew LOCA in DW Set Event Trigger 5 to true.

Recognize Drywell pressure is increasing.

This will initiate the LOCA RO:

INFO: From the LOCA, ~2

Perform a manual scram prior to 2 psig in the Drywell.

Booth Instructor:

min to 1st alarm,

Perform IPOI 5 actions

~1 min to 2#, When the HPCI trip annunciator comes in

Perform Fast Power Reduction, if time available

~14 min to (1C03C A-4, A-6, and B-3):

280F Set Event Trigger 10 to TRUE CRS This will set these annunciators to ON,

Enter AOP 573, but determine that DW pressure is rising too quickly for thus avoiding these alarms coming in and AOP actions to be taken.

out for the rest of the scenario.

If time available, direct a Fast Power Reduction per IPOI 4.

Direct Manual Scram prior to automatic scram

Enter EOP 1 and EOP 2 on High Drywell Pressure 2 psig.

Event 6 The CRS will direct and the Crew will perform the following actions from EOP 2 DW pressure rising

Initiate torus sprays when torus pressure above 2 psig (before 11 psig)

Initiate torus cooling when directed

Install EOP Defeat 4 when directed

When directed, initiate DW sprays CT: While in the safe region of the drywell spray initiation limit, and before The CRS will direct and the Crew will perform the following actions from drywell temperature reaches 280 °F, EOP 1 initiate drywell sprays.

Maintain RPV level between 170 and 211 inches

Install Defeat 11, over ride DW N2.

Maintain RPV pressure stable 2008 NRC ILT ESG 2 page 14 of 18

Rev. 0 2008 NRC Scenario #2 SCENARIO TIME-LINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 7 Booth Instructor: RO Loss of High When the crew is spraying the DW, then

Recognize the loss of HP FW injection systems, and determine that RCIC Pressure Feed Look to the status of the condensate cannot maintain RPV level (RCIC stays pumps. IF one of the condensate pumps

Perform ALC when injection systems are lined up and available running) is SECURED, THEN OVERRIDE that

Start 2nd CRD pump IAW QRC when directed Pump handswitch to OFF by using:

Start SBLC IAW QRC when directed Event Trigger 12 for the A pump

Make frequent reports of RPV water level INFO: from the Event Trigger 13 for the B pump

Attempt to restart the Feed and Condensate train that was secured loss of FW, ~6 THEN: earlier.

minutes to LO-LO-LO level, ~2 Activate the Event Trigger for the RUNNING condensate pump: BOP minutes to +15,

~1.5 minutes to

Lockout ADS when directed Event Trigger 7 for the A pump

-25.

Make frequent reports of RPV water level Event Trigger 8 for the B pump

Close MSIVs prior to 64 inches (or verify at 64 inches)

This will insert a trip of the running condensate pump(s), and prevent a start of the pump that was not running. CRS

Recognize the failure of RCIC to maintain RPV water level and enter ALC Role Play as person sent to investigate

Direct operator actions to lock out ADS condensate pumps:

Direct Crew Response for performance of ALC when injection systems Pumps/motors appear to have nothing are lined up and available wrong with them.

Circuit Breaker(s) for pumps that have

Direct injection with second CRD pump tripped on overload (wont reset)

Direct injection with SBLC Role Play as person sent to manually shut

Brief crew on expected actions (ALC ED and reflood actions) the breaker for the condensate pump that wont start, report that the breaker wont shut.

Role Play as NSPEO for restart of other condensate pump 2008 NRC ILT ESG 2 page 15 of 18

Rev. 0 2008 NRC Scenario #2 SCENARIO TIME-LINE TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 8

When reactor water level cannot be maintained greater than +15".

ALC ED

Lockout ADS (if not already performed)

Line up at least 2 injection subsystems.

Wait until reactor level drops to +15", and ED before -25".

Open 4 ADS SRVs

Restore and maintain level to 170 to 211 inches.

CRS:

CT ALC: With Reactor pressure greater Perform ED after +15 inches and prior to -25 inches.

than the shutoff head of the low pressure systems, after RPV water level reaches +15", and before level reaches

-25" if any pump is lined up and available for injection, initiate an emergency depressurization.

When the plant Booth Instructor:

is stable and FREEZE the simulator and announce to reactor the crew that the scenario is complete.

pressure and level are being controlled IAW EOP 1

- - END OF SCENARIO ***

- - REVIEW SCENARIO OBJECTIVES WITH THE OPERATORS ***

2008 NRC ILT ESG 2 page 16 of 18

SEG Validation Checklist SEG ________2008 NRC ILT Scenario #2____________ Rev. ______0_______

Correct IC or plant status identified.

Shift turnover forms filled out (both CRS/OSM and NSOE) if required.

Additional documents are prepared (STPs, Work Orders, LCO Paperwork).

Tasks and Objectives have been verified to be correct.

Plant PRA initiating events, important equipment and important tasks are identified.

SOMS tags identified and included in setup instructions.

Special setup instructions identified; handswitch manipulations, procedure markups, alarm borders, 3D case available, computer points substituted, etc.

Setup files correctly called out.

Malfunction list is accurate.

Override list is accurate.

Remote function list is accurate.

Event triggers are accurate.

Time/Notes section is accurate and includes all reasonable cues that may be given to initiate an action. Cues are unambiguous and provide a definitive moment to take action.

Instructor Activity section is accurate and complete:

Actions are clearly defined for Booth or Floor instructor.

Role-playing is clearly noted.

The sequence of events is completely and concisely narrated even if it takes no instructor action.

Automatic actions that require verification are noted.

Reasonable alternate paths are considered and included.

Event trigger activation is distinguished from narrative text (Bold font)

Noun descriptions of actions that occur on event trigger initiation are complete, for example set ET 3 to TRUE which activates malfunction SW21C resulting in a loss of the C Well Water Pump.

Other simulator control actions are clearly distinguished from narrative text, for example after drywell temperature reaches 280 deg. F SNAP the simulator to IC 0.

Student and Instructor copies of worksheets or other training activities are verified correct and electronically attached to the file if appropriate.

2008 NRC ILT ESG 2 Page 17 of 18